IDENTIFYING UNCERTAINTY CONTRIBUTIONS TO THE SEISMIC FRAGILITY ASSESSMENT OF A NUCLEAR REACTOR STEAM LINE

P. Gehl, Marine Macilhac-Fradin, J. Rohmer, Y. Guigueno, N. Rahni, J. Clément
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引用次数: 1

Abstract

In nuclear applications, fragility curves are an essential element of the seismic probabilistic safety assessment that is performed at the level of the power plant. These statistical tools establish the link between the probabilistic seismic hazard loading at the site and the required performance of the plant's safety functions. In this context, the fragility model formalized by Kennedy & Ravindra (1984) proposes to account for the aleatory randomness and the epistemic uncertainty generated by various sources of variability, such as the representation of the seismic input or the assumptions in the structural model and in the loading patterns. Therefore, this study investigates the relative contributions of such variables to the dispersion of the resulting fragility functions, while ensuring the separation between aleatory and epistemic uncertainty sources, as advocated by the standards in effect in the nuclear industry. To this end, a coupled model of a supporting structure and an anchored steam line is considered and computed with the finite-element CAST3M software (Rahni et al., 2017). The failure criterion is related to the exceedance of a given effort value at a point of the steam line corresponding to a vertical stop. A coupled of hundreds of three-component ground-motion records are applied at the base of the model, in order to perform non-linear time-history analyses. The record selection follows the conditional spectrum method (Lin et al., 2013), in order to scale the records while ensuring the hazard consistency, through the identification of reference earthquake scenarios for each predefined hazard level. As a result, dozens of ground-motion parameters are tested as potential intensity measures (IMs), with respect to state-of-the-art indicators measuring efficiency or sufficiency. Some couples of ground-motion parameters are assembled as vector-valued IMs, in order to generate so-called fragility surfaces: these multi-variate functions may then be reinterpreted as single-IM fragility curves, where the conditional distribution of the secondary IM with respect to the main one generates additional confidence intervals for the fragility curve. It is thus shown that the aleatory randomness due to record-to-record variability may be partially transferred to an epistemic uncertainty contribution. This variability is then put in perspective with other sources of uncertainty due to modelling assumptions, such as the variability in the mechanical parameters of the model or the angle of loading of the seismic input.
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确定不确定性对核反应堆蒸汽管线地震易损性评估的贡献
在核应用中,易损性曲线是在电厂一级进行地震概率安全评估的基本要素。这些统计工具建立了现场概率地震危险载荷与工厂安全功能所需性能之间的联系。在这种情况下,Kennedy & Ravindra(1984)提出的脆弱性模型考虑了由各种可变性来源(如地震输入的表示或结构模型和加载模式中的假设)产生的随机性和认知不确定性。因此,本研究调查了这些变量对由此产生的脆弱性函数的分散的相对贡献,同时确保了核工业中有效标准所倡导的选择性和认知不确定性源之间的分离。为此,考虑了支撑结构和锚定蒸汽管线的耦合模型,并使用有限元CAST3M软件进行了计算(Rahni et al., 2017)。失效准则是与蒸汽管线某一点上与垂直停止相对应的超出给定的努力值有关。为了进行非线性时程分析,在模型的基础上应用了数百个三分量地震动记录的耦合。记录选择遵循条件谱法(Lin et al., 2013),通过识别每个预定义危险级别的参考地震情景,在保证灾害一致性的同时对记录进行缩放。结果,数十个地面运动参数作为潜在强度测量(IMs)进行了测试,以衡量效率或充分性的最先进指标。为了生成所谓的脆弱性曲面,一些地面运动参数对被组装成矢量值的脆弱性曲面:这些多变量函数然后可以被重新解释为单一脆弱性曲线,其中次级脆弱性相对于主要脆弱性的条件分布为脆弱性曲线产生额外的置信区间。这表明,由于记录到记录的可变性,可部分转移到认识的不确定性贡献的随机性。然后,将这种可变性与建模假设引起的其他不确定性来源(例如模型力学参数的可变性或地震输入的加载角度)联系起来。
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